ML20128P676

Chapter 1 of RESAR-SP/90 Westinghouse Advanced PWR Module 11, Radiation Protection, Introduction & General Description of Plant

ML20128P676
Person / Time
Site:	05000601
Issue date:	06/30/1985
From:	WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
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ML19304B384	List: ML20128P639 ML20128P653 ML20128P676 ML20128P684 ML20128P690 ML20128P703 ML20128P727 ML20128P742 ML20128P756 ML20128P780 ML20128P810 ML20128P823 ML20128P841 ML20128P852 ML20128P859 ML20128P876 ML20128P888 ML20128P891 NRC-85-3047, Forwards Nonproprietary & Proprietary RESAR-SP/90 Westinghouse Advanced PWR Module 11, Radiation Protection. Application for Withholding Proprietary Info (Ref 10CFR2.790) Encl
References
NUDOCS 8507260478
Download: ML20128P676 (6)

Text

1.0 INTRODUCTION

AND GENERAL DESCRIPTION OF PLANT

1.1 INTRODUCTION

The Westinghouse Electric Corporation (hereinafter referred to as Westinghouse) has developed this Reference Safety Analysis Report (RESAR-SP/90) for the Westinghouse Advanced Pressurized Water Reactor (WAPWR) as part of its continuing efforts toward design and licensing standardization of nuclear power plants. RESAR-SP/90 is a standard safety analysis report submitted initially for Preliminary Design Approval (PDA) in accordance with Appendix 0, " Standardization of Design; Staff Review of Standard Designs," to Part 50 of Title 10 of the Code of Federal Regulations (hereinafter referred to as 10CFR). The ultimate objective is to obtain a Final Design Approval (FDA) of RESAR-SP/90 followed by a rulemaking proceeding and design certification.

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WAPWR-RP 1.1-1 JUNE, 1985 2997e:1d 8507260478 850712 DR ADOCK0500g1

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1.2 GENERAL PLANT DESCRIPTION 1.2.2 Principal Desian Criteria i

RESAR-SP/90 is designed to comply with 10 CFR Part 50, Appendix 'A, " General Design Criteria for Nuclear Power Plants." The specific applications of l General Design Criteria to RESAR-SP/90 are discussed in Section 3.1 of RESAR-SP/90 Module 7. " Structural / Equipment Design.

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I WAPWR-RP 1.2-1 JUNE, 1985 t 2997e:1d

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f 1.6 MATERIAL INCORPORATED BY REFERENCE

., . The WAPWR Radiation Protection Module incorporates, by reference, certain topical reports. The topical reports, listed in Table 1.6-1, have been filed d

previously in support of other Westinghouse applications.

The legend for the review status code letter follows:

A - . U.S. Nuclear Regulatory Connission review complete; USNRC acceptance letter issued.

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U.S. Nuclear Regulatory Connission accepted as part of the Westinghouse emergency core cooling system (ECCS) evaluation model only; does not constitute acceptance for any purpose other than for ECCS analyses.

, 8 - Submitted to USNRC as background information; no undergoing formal USNRC review.

i 0 - On file with USNRC: older generation report with current validity; not actively under formal USNRC review.

< 9-U - Actively under formal USNRC review.

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,I WAPWR-RP 1.6-1 JUNE, 1985 2997e:1d s

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i l TABLE 1.6-1 MATERIAL INCORPORATED BY REFERENCE i

Westinghouse SAR Topical Revision Section Submitted Reviet Report No. Title Number Reference to the NRC Statu!

l WCAP-8370 Westinghouse Water Reactor Divi- Rev. 9A 17.1 2/81 A i sions Quality Assurance Plan Amend. 1 1

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WAPWR-RP 1.6-2 JUNE, 1985 2997e:1d i

4 1.8 CONFORMANCE WITH THE STANDARD REVIEW PLAN In accordance with 10CFR50.34(g), Table 1.8-1 of each PDA module identifies _

-and evaluates deviations from the acceptance criteria of those sec,tions of the NRC Standard Review Plan (NUREG-0800) pertinent to the subject module. Table 1.8-1 provides this list for the " Radiation Protection".

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WAPWR-RP 1.8-l JUNE,1985 2997e:1d I

r TABLE 1.8-1 STANDARD REVIEW PLAN DEVIATIONS SRP Acceptance Criteria Deviation Section SRP 12.3 ? The design of the fuel pool 12.3.4.1 12.4 ( racks precludes criticality Describe the radiation instru- under all postulated normal mentation that will be used to and accident conditions. There-meet the criticality accident fore, criticality monitors, monitoring requirements of as required by 10 CFR 70.24 5 70.24 of 10 CFR Part 70 for and Regulatory Guide 8.12, are storage area for new fuel. not needed. l O

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O O 1.B-2 WAPWR-RP JUNE, 1985 2997e:1d

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